Refine your search:     
Report No.
 - 
Search Results: Records 1-9 displayed on this page of 9
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

JAEA Reports

None

Koshizuka, Seiichi*; *; Okano, Yasushi; *; Yamaguchi, Akira

JNC TY9400 2000-012, 91 Pages, 2000/03

JNC-TY9400-2000-012.pdf:2.82MB

no abstracts in English

Journal Articles

Transmission of evacuation recommendation during a LPG leak incident at Higashinada ward, Kobe city in the Great Hanshin-Awaji Earthquake Disaster

Umemoto, Michitaka; *; Kobayashi, Kensuke; Ishigami, Tsutomu; *; *; *

Chiiki Anzen Gakkai Rombun Hokokushu, (7), p.228 - 233, 1997/11

no abstracts in English

JAEA Reports

None

*; *; ; *; *; Ito, Kenji

PNC TJ2164 97-004, 38 Pages, 1997/10

PNC-TJ2164-97-004.pdf:3.34MB

JAEA Reports

None

Shimoyama, Kazuhito; Usami, Masayuki; Miyake, Osamu; ; ; Tanabe, Hiromi

PNC TN9450 97-007, 81 Pages, 1997/03

PNC-TN9450-97-007.pdf:1.72MB

None

JAEA Reports

None

Kawada, Koji; ; Tanabe, Hiromi; ; Miyake, Osamu

PNC TN9450 97-005, 145 Pages, 1997/03

PNC-TN9450-97-005.pdf:2.48MB

None

JAEA Reports

None

*; Miyahara, Shinya

PNC TN9420 94-005, 74 Pages, 1994/03

PNC-TN9420-94-005.pdf:2.89MB

no abstracts in English

JAEA Reports

None

PNC TN9600 93-010, 18 Pages, 1993/05

PNC-TN9600-93-010.pdf:5.59MB

None

JAEA Reports

Design study of key technology for large LMFBR (II); Sodium fire analysis

Morii, Tadashi*; Himeno, Yoshiaki

PNC TN9410 86-066, 27 Pages, 1986/06

PNC-TN9410-86-066.pdf:3.68MB

Sodium fire analysis has been performed for a large FBR to evaluate pressure and temperature transients and mass of burned sodium in case of a primary sodium leak accident. The major analytical conditions are as follows: [Position of sodium leak : Hot leg of primary coolant system] [Cross-sectional area of a leak hole : 1 cm$$^{2}$$] [Concrete cooling system : operated (just before failure), shut down (after sodium leak)] The most representative results gained through the present study are as follows: [Maximum Gas Pressure : 0.029 kg/cm$$^{2}$$2 -g (0.5 hr after a leak)] [Total Mass of Burned Sodium : 1.5 ton (3% of total leak sodium)] [Maximum Concrete Temperature (beneath sodium pool) : 140$$^{circ}$$C (100 hr after a leak) These results indicate that a concrete cooling system to present abnormal temperature rise that may occure due to heat transfer from the hot primary coolant system was shown to be effective even in the accident conditions. However, further study will be needed to evaluate water release rate from the heated concrete.

Oral presentation

Radioactivity leak accident at the hadron experimental facility and the reformation of the safety management system in J-PARC

Ishii, Tetsuro

no journal, , 

Radioactivity leak accident occurred at the Hadron Experimental Facility of J-PARC revealed serious problems on safety organization and emergency actions as well as problems on hardware. We have reviewed safety management system entirely and reformed it as follows. (1) The responsibility of facility manager and command line was clearly defined. (2) Radiation safety review system was reinforced. (3) "Alert Status" between "Standard Status" and "Emergency Status" was introduced for gathering of responsible personnel and integration and sharing information. (4) Criteria and procedures for actions in emergency and notification were clarified.

9 (Records 1-9 displayed on this page)
  • 1